Measurement of void fraction distribution in a 44 fuel bundle under high pressure condition for validation of two-phase CFD code

二相流解析コード検証データ取得のための高圧条件における44模擬燃料集合体内ボイド率分布計測

永武 拓 ; 柴田 光彦 ; 上澤 伸一郎  ; 小野 綾子 ; 吉田 啓之  

Nagatake, Taku; Shibata, Mitsuhiko; Uesawa, Shinichiro; Ono, Ayako; Yoshida, Hiroyuki

過酷事故を含む事故時の炉心冷却を評価する上では、ポンプなどが停止した低流速条件での気液二相流の挙動の把握が重要となる。本研究では低流速時における、炉心内の気液二相流挙動を実験的に把握するため、二相流解析コードTPFIT及びACE3Dの開発・改良、及び検証データ取得を目的としたワイヤーメッシュセンサーを用いた模擬燃料集合体内ボイド率分布の計測を行っている。本報では、44の非発熱模擬燃料集合体試験装置を用いて、蒸気-水系二相流のボイド率分布を、0.1MPaから2.6MPaまでの範囲において計測した結果について報告する。

In the Fukushima Daiichi Nuclear Power Plant accident, reactor cores were cooled by natural circulation due to pump trip. To investigate the accident progress of the Fukushima Daiichi Nuclear Power Plant, it is important to understand the thermal hydraulic behavior in reactor cores including fuel bundles. Flow rate inside cores was relatively low in the natural circulation conditions, then, thermal-hydraulic behavior in the fuel bundles was different from that in the normal operating conditions. To evaluate thermal hydraulic behavior under the accidental conditions, we are developing the numerical simulation codes named TPFIT and ACE3D. These codes are based on two-phase computational fluid dynamics and can simulate the two-phase flow inside fuel bundles including low flow rate condition. Before applying these codes to the thermal-hydraulic behavior, the applicability of these codes must be confirmed. Then, in this study, in order to obtain a validation data for TPFIT and ACE3D code, thermal hydraulic experiment was performed by using test section with a simulated fuel bundle with 44 unheated rods. In this simulated fuel bundle, there were wire mesh sensors, and void fraction distribution data inside the simulated fuel bundle under high pressure condition (max. 2.6 MPa) was obtained. The one of the advantage of wire mesh sensor is that a void fraction distribution of cross section at the same time can be measured. In this paper, void fraction distribution of two-phase flow in a simulated fuel bundle under high pressure condition are reported.